US4364859A - Method for producing oxide powder - Google Patents

Method for producing oxide powder Download PDF

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Publication number
US4364859A
US4364859A US06/168,144 US16814480A US4364859A US 4364859 A US4364859 A US 4364859A US 16814480 A US16814480 A US 16814480A US 4364859 A US4364859 A US 4364859A
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US
United States
Prior art keywords
nitrate solution
microwave power
gas
uranium
thorium
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Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
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US06/168,144
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English (en)
Inventor
Katsuyuki Ohtsuka
Jin Ohuchi
Yoshiharu Takahashi
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Doryokuro Kakunenryo Kaihatsu Jigyodan
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Doryokuro Kakunenryo Kaihatsu Jigyodan
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/004—Compounds of plutonium
    • C01G56/005—Oxides; Hydroxides
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/007—Compounds of transuranic elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05B—ELECTRIC HEATING; ELECTRIC LIGHT SOURCES NOT OTHERWISE PROVIDED FOR; CIRCUIT ARRANGEMENTS FOR ELECTRIC LIGHT SOURCES, IN GENERAL
    • H05B6/00—Heating by electric, magnetic or electromagnetic fields
    • H05B6/64—Heating using microwaves
    • H05B6/80—Apparatus for specific applications
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05B—ELECTRIC HEATING; ELECTRIC LIGHT SOURCES NOT OTHERWISE PROVIDED FOR; CIRCUIT ARRANGEMENTS FOR ELECTRIC LIGHT SOURCES, IN GENERAL
    • H05B2206/00—Aspects relating to heating by electric, magnetic, or electromagnetic fields covered by group H05B6/00
    • H05B2206/04—Heating using microwaves
    • H05B2206/045—Microwave disinfection, sterilization, destruction of waste...
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a process for heat treatment of a radioactive substance by microwave power and more particularly, to a heat treatment process for the production of oxide powders suitable for the manufacture of nuclear fuel pellets.
  • Typical conventional methods of producing oxide powders of uranium, thorium, plutonium or the like substances include a direct denitration method, a sol-gel method, a precipitation method and so forth. These methods have, however, advantages and disadvantages, and are not satisfactory.
  • the direct denitration method comprises heating nitrate solutions of these substances to convert the nitrate solutions to oxide powders and, according to the type of heating, this method further employs a fluidized bed or heater.
  • a fluidized bed or heater In the direct denitration method using a fluidized bed, there are produced hollow particles which are unsuitable for raw materials for fuel pellets of high density.
  • This method has further disadvantages in that a large amount of gas is discharged due to the use of fluidizing gas, that a large-sized apparatus for processing the discharging gas is required, and that additional oxide powders are necessitated as a fluidizing medium and as seeds.
  • the sol-gel method comprises, in the case where uranium oxide, for example, is produced, adding hexamethylenetetramine to a uranyl nitrate solution, dripping the thus obtained solution into paraffin at 95° C. to make sol and gel, and drying it to produce oxide powder.
  • This method presents problems in that it is difficult to define and control conditions for producing oxide powder having a desired particle size, and that fuel pellets made of the thus obtained powder provide a larger degree of swelling.
  • the precipitation method consists of preparing a nitrate solution of uranium, thorium, plutonium or the like substances, adding ammonia to the solution so as to cause precipitation of hydroxides, subjecting the precipitate to solid-liquid separation, drying the separated solid and effecting roast-reduction of the dried solid.
  • This precipitation method is most preferred because it can provide powders of a high activity due to good sinterability, as well as a smaller swelling of the pellet.
  • This method requires a large number of steps such as solid-liquid separation, drying, roast-reduction and so on as stated before, resulting inevitably in enlargement and complication of the production equipment, as well as an increase of the dosage of radioactive rays to which workers are subjected. If remote control and automation of the process are adopted for reducing the dosage to the workers, the equipment is inconveniently rendered further complicated. During maintenance of such highly complicated equipment, the chance of increased dosage will be increased.
  • the process since the substance to be treated is radioactive, the process must be executed under a specific management, and the substance must be handled in a cell or globe box of gas-tight construction having a specific evacuation system.
  • the simplification and improved durability of the processing equipment are essential particularly in this case, because the control and protective maintenance of the equipment are made indirectly.
  • the reduced number of process units is preferred also from the view points of decrease of dosage to workers and reduction of generation of radioactive byproducts which are to be disposed.
  • An object of the present invention is to provide a method for heat treatment of radioactive substances.
  • Another object of the present invention is to provide a heating process making use of microwave power, suitable for use in the production of oxide powders for nuclear fuel pellets having a high activity.
  • an apparatus for heat treatment of a radioactive substance by using microwave power which comprises a shield box, a microwave power application chamber disposed in the shield box, a microwave power generator disposed at the outside of the shield box, and a waveguide tube extending through the wall of the shield box between the microwave power generator and the microwave power application chamber.
  • the microwave power application chamber is provided with a passage for the supply of the radioactive substances to be treated and/or a passage for discharging volatile substances released from the radioactive substances under heat treatment.
  • the waveguide tube is closed internally by means of a wave guiding material which prevents substances from moving from the microwave power application chamber to the microwave power generator.
  • a method for producing oxide powder suitable for the manufacture of nuclear fuel pellets comprises preparing a nitrate solution of uranium, thorium, plutonium or the like substance, and applying microwave power to the nitrate solution to directly convert the nitrate solution to oxide powder, without necessitating any adjustment of the concentration of the nitrate solution and without taking the step of solid-liquid separation. It is also possible to directly convert a mixture of two or three of the above-mentioned nitrate solutions to a powder mixture of their oxides.
  • an apparatus for performing the process of the present invention has a shield box 1 which may be a globe box or a cell, in which a microwave power application chamber 2 is disposed.
  • a microwave power generator 3 is positioned at the outside of the shield box 1.
  • the microwave power application chamber 2 and the microwave power generator 3 are connected to each other by means of a waveguide tube 4 which extends through the wall of the shield box 1.
  • the microwave power application chamber 2 accommodates a heating vessel 5 provided with a port 6 for the supply of radioactive substance to be treated and a gas discharging port 7 which is connected, through a pipe, to a condenser 8.
  • the condenser 8 in turn communicates with an exhaust blower 10, through a gas scrubber 9.
  • a shielding plate 11 is disposed in the waveguide tube 4 by which the microwave power application chamber 2 and the microwave power generator 3 are connected to each other.
  • the shielding plate 11 is made of a material having a good wave guiding nature and a high corrosion resistance, e.g. fluorine-contained resin, silicone resin, glass, ceramics and so forth, and is adapted to prevent the radioactive substance and corroding gas in the chamber 2 from being transferred and diffused into the microwave power generator 3, although it permits the electromagnetic wave coming from the generator 3 to pass therethrough.
  • a solution or slurry containing uranium, thorium, plutonium or the like radioactive substance is introduced into the heating vessel 5 through the supply port 6. Then an electromagnetic wave of a microwave power generated by the microwave power generator 3 is applied to the solution or slurry, so as to heat the latter.
  • the gas released from the solution or slurry as a result of the heating is discharged through the discharging port 7 into the condenser 8 in which the condensate is separated from the gas.
  • the gas is then scrubbed in the scrubber 9, and is exhausted by means of the exhaust blower 10.
  • the powders formed in the heating vessel 5 can be extracted continuously or batchwise.
  • the microwave power heating utilized in the present invention is of the so-called internal heating method in which the substances to be heated themselves generate the heat. Therefore, the heating is not affected by heat conductivity, so that no temperature gradient is formed. As a result, this heating method inherently affords a homogeneous heating at a high efficiency of utilization of energy, which in turn permits a roast-reduction at a low temperature, so as to ensure a high sinterability of the oxide powders for fuel pellets.
  • Hydroxides are precipitated by respectively adding ammonia to the above-mentioned four nitrate solutions. These precipitates can be directly converted into oxide powders by the heating operation, without necessitating the step of filtration.
  • Thorium carbonate is precipitated by adding ammonium carbonate to the thorium nitrate solution. This thorium carbonate can be directly converted into thorium dioxide by the heating operation, without necessitating the step of filtration.
  • Waste liquid or slurry containing uranium, thorium, plutonium, and other transuranium elements, as well as fission products, can be directly dried or calcined.
  • the use of powders of high activity is essential for the production of highly dense oxide pellets of uranium, thorium or plutonium.
  • highly active powders is not essential in the production of pellets of low density.
  • the pellets produced without using highly active powders have an impractically low density of the matrix as a whole, often resulting in a densification or the like unfavourable phenomena.
  • Such pellets are not suitable for use as fuel pellets. Therefore, the powders of high activity are used also in the production of pellets of low density. Namely, a density lowering agent such as polyethylene is added to the powders of high activity, and the powders are molded together with this agent.
  • the density lowering agent is evaporated during sintering, so that pores may be uniformly distributed in the pellet so as to lower the density of the produced pellet. It is therefore essential to use powders of high density, but also in the production of pellets of low density as well.
  • the process of the invention is particularly useful for the production of such powders of high activity.
  • 0.2 l of uranyl nitrate solution having a uranium concentration of 500 g/l was put in a vessel made of a ceramic. Then, a microwave power of 2450 MHz and 480 W power was applied to the solution for 45 minutes, so as to reduce the latter into blocks and powders. These blocks and powders were removed from the apparatus and were roasted at 700° C. for two hours in a separate roaster and were then treated for four hours in a hydrogen reducing atmosphere at 720° C. The resulting uranium dioxide was then processed in a mortar, and was molded at a molding pressure of 2 ton/cm 2 . The molded uranium dioxide powders were finally sintered at 1650° C., so as to become a uranium dioxide pellet having a density of 93.0% of the theoretical density.
  • Ammonia was added to 0.2 l of uranyl nitrate solution containing 500 g/l of uranium, so as to cause a precipitation of ammonium diuranate.
  • the precipitate was then put in a vessel made of a ceramic, without being subjected to solid-liquid separation. Subsequently, a microwave power of 2450 MHz and 480 W power was applied to the precipitate in the vessel for 45 minutes, and a pellet of uranium dioxide was produced in the same way as Example 1. This pellet had a density of 92% of the theoretical density, and no extraordinariness of appearance was found.
  • 80 ml (116 g) of slurry containing ammonium nitrate, iron hydroxide, aluminum hydroxide and tri-iron tetraoxide was prepared as a simulative sample of slurry produced in a plutonium waste liquid disposal process. 7 g of oxide powders were obtained, as a result of application of a microwave power of 2450 MHz and 480 W power for 18 minutes.
  • the apparatus for carrying out the process of the invention and having the construction hereinbefore described has a large treating capacity for its reduced size.
  • the space required for the globe box can be reduced to 1/6, while the treating capacity is increased by five times.
  • the installation space of the apparatus as a whole can be reduced to 1/30.
  • such apparatus has a highly simplified construction within the shield box, is quite easy to maintain, and requires less frequent maintenance work. Owing to these features, such apparatus can be used quite suitably in the heat treatment of radioactive substances.
  • such apparatus can advantageously be used particularly in the production of oxide powders for fuel pellets, because the use of the apparatus affords production of highly dense spherical powders of small particle size by a simplified process. Further, the apparatus can effectively be used in the solidification treatment of waste liquid containing transuranium elements and fission products.

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  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Inorganic Chemistry (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • Electromagnetism (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Constitution Of High-Frequency Heating (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
US06/168,144 1978-03-13 1980-07-14 Method for producing oxide powder Expired - Lifetime US4364859A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
JP2852678A JPS54121442A (en) 1978-03-13 1978-03-13 Microwave heating device for radioactive material
JP53-28526 1978-03-13

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US06018320 Division 1979-03-07

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US (1) US4364859A (enrdf_load_stackoverflow)
JP (1) JPS54121442A (enrdf_load_stackoverflow)
BE (1) BE874748A (enrdf_load_stackoverflow)
DE (1) DE2909858C2 (enrdf_load_stackoverflow)
FR (1) FR2420269A1 (enrdf_load_stackoverflow)
GB (1) GB2019178B (enrdf_load_stackoverflow)

Cited By (28)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4439402A (en) * 1980-12-16 1984-03-27 Tokyo Shibaura Denki Kabushiki Kaisha Nuclear fuel conversion systems
US4444723A (en) * 1981-04-16 1984-04-24 Tokyo Shibaura Denki Kabushiki Kaisha Denitration systems
US4563335A (en) * 1982-12-21 1986-01-07 Doryokuro Kakunenryo Kaihatsu Jigyodan Apparatus for continuously concentrating and denitrating nitrate solution by microwave
US4627937A (en) * 1982-11-26 1986-12-09 Kernforschungszentrum Karlsruhe Gmbh Process for denitrating nitric acid and actinide containing waste solutions while simultaneously separating the actinides
US4671952A (en) * 1985-02-20 1987-06-09 C-I-L Inc. Vaporizing liquid sulfur dioxide with microwave radiation
US4671951A (en) * 1984-03-23 1987-06-09 C-I-L Inc. Purification and reconcentration of waste sulphuric acid
US4673560A (en) * 1985-02-20 1987-06-16 C-I-L Inc. Generation of sulphur trioxide from oleum using microwave energy
US4687601A (en) * 1983-11-25 1987-08-18 Comurhex Process for the preparation of pulverulent metallic oxides from metallic nitrates
US4737610A (en) * 1985-03-30 1988-04-12 Hugo Petersen Gesellschaft fur verfahrenstechnischen Anlagenbau mbH & Co. KG Method and apparatus for the desorption of an adsorption agent that is loaded with noxious material
US4784686A (en) * 1987-04-24 1988-11-15 The United States Of America As Represented By The United States Department Of Energy Synthesis of ultrafine powders by microwave heating
US4871479A (en) * 1986-03-25 1989-10-03 Comurhex Societe Pour La Conversion De L'uranium En Metal Et Hexafluorure Process for producing sintered mixed oxides which are soluble in nitric acid from solutions of nitrates
US4873031A (en) * 1986-06-18 1989-10-10 Mitsubishi Kinzoku Kabushiki Kaisha Method of controlling the crystal grain size of uranium dioxide pellet
AT391848B (de) * 1988-06-22 1990-12-10 Andritz Ag Maschf Verfahren und vorrichtung zur gewinnung von metalloxiden
US4981616A (en) * 1988-09-05 1991-01-01 Doryokuro Kakunenryo Kaihatsu Jigyodan Spent fuel treatment method
US5003143A (en) * 1990-04-09 1991-03-26 Progressive Recovery, Inc. Microwave sludge drying apparatus and method
US5154899A (en) * 1991-06-28 1992-10-13 Sturcken Edward F Metal recovery from porous materials
US5278379A (en) * 1990-08-14 1994-01-11 Doryokuro Kakunenryo Kaihatsu Jigyodan Continuous denitration apparatus which uses microwave heating
US5411712A (en) * 1993-02-24 1995-05-02 General Electric Company Batch system for microwave desorption of adsorbents
US5464571A (en) * 1993-07-09 1995-11-07 Japan Atomic Energy Research Institute Once-through nuclear reactor fuel compounds
US5581589A (en) * 1994-04-14 1996-12-03 Japan Atomic Energy Research Institute Method and apparatus for producing gel particles
FR2757993A1 (fr) * 1996-12-27 1998-07-03 Doryokuro Kakunenryo Procede de fabrication de boulettes de combustible nucleaire
US6110437A (en) * 1995-12-12 2000-08-29 Comurhex (S.A.) Method for preparing a mixture of powdered metal oxides from nitrates thereof in the nuclear industry
US6228337B1 (en) 1998-12-02 2001-05-08 Cameco Corporation Method for reducing uranium trioxide
US6437303B1 (en) * 1998-02-19 2002-08-20 Siemens Aktiengesellschaft Method and furnace for microwave sintering of nuclear fuel
CN102441359A (zh) * 2011-09-30 2012-05-09 常熟市申华化工贸易有限公司 一种化工反应罐
CN103077759A (zh) * 2013-01-11 2013-05-01 吕应中 全能铀-钍转化-增殖堆装置及生产核燃料铀-233的方法
RU2603359C1 (ru) * 2015-11-26 2016-11-27 Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Способ получения оксидов урана
US20190193152A1 (en) * 2016-08-23 2019-06-27 Paul Scherrer Institut Aqueous additive production method for the fabrication of ceramic and/or metallic bodies

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Publication number Priority date Publication date Assignee Title
US4389355A (en) * 1981-07-23 1983-06-21 The Babcock & Wilcox Company Sintering UO2 and oxidation of UO2 with microwave radiation
NL8203357A (nl) * 1981-09-11 1983-04-05 Babcock & Wilcox Co Werkwijze voor het bereiden van een sinterbaar poeder van uraniumdioxide.
DE3348380C2 (de) * 1982-05-06 1995-06-14 Doryokuro Kakunenryo Wärmebehandlungsvorrichtung zum fortlaufenden Behandeln eines radioaktiven Stoffes
JPS58191998A (ja) * 1982-05-06 1983-11-09 動力炉・核燃料開発事業団 環状槽型マイクロ波加熱装置
JPH0795111B2 (ja) * 1985-10-01 1995-10-11 動力炉・核燃料開発事業団 マイクロ波加熱脱硝方法および装置
DE3805063A1 (de) * 1988-02-18 1989-08-31 Kernforschungsz Karlsruhe Verfahren zur herstellung von kernbrennstoff-mischoxiden aus einer nitrat-loesung
IT1237806B (it) * 1989-12-21 1993-06-17 Temav Spa Procedimento per la preparazione di polveri fini di alluminio nitruro da al303 e carbone
IT1237803B (it) * 1989-12-21 1993-06-17 Temav Spa Procedimento per la preparazione di polveri fini di alluminio nitruro
DE4002533A1 (de) * 1990-01-29 1991-08-01 Reinhard Schulze Aufnahmevorrichtung fuer die beaufschlagung von behandlungsguetern mit mikrowellenfeldern
JP2798856B2 (ja) * 1992-09-16 1998-09-17 動力炉・核燃料開発事業団 連続脱硝装置
JPH08184690A (ja) * 1994-12-28 1996-07-16 Power Reactor & Nuclear Fuel Dev Corp 核燃料用粉末の製造方法
FR2803283B1 (fr) * 2000-01-03 2002-03-29 Cogema Procede et dispositif pour la transformation en continu de l'oxalate de plutonium en oxyde de plutonium
RU2281573C1 (ru) * 2005-06-02 2006-08-10 ОАО "Тантал" Способ матричной иммобилизации промышленных отходов радиохимических и химико-металлургических производств
JP5785675B2 (ja) * 2011-02-14 2015-09-30 三菱マテリアル株式会社 核燃料ペレット製造用粒子の製造方法
US9646729B2 (en) * 2013-01-18 2017-05-09 Westinghouse Electric Company Llc Laser sintering systems and methods for remote manufacture of high density pellets containing highly radioactive elements
CN116525170A (zh) * 2023-01-31 2023-08-01 中国原子能科学研究院 一种二氧化钚的溶解方法

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Cited By (32)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4439402A (en) * 1980-12-16 1984-03-27 Tokyo Shibaura Denki Kabushiki Kaisha Nuclear fuel conversion systems
US4444723A (en) * 1981-04-16 1984-04-24 Tokyo Shibaura Denki Kabushiki Kaisha Denitration systems
US4627937A (en) * 1982-11-26 1986-12-09 Kernforschungszentrum Karlsruhe Gmbh Process for denitrating nitric acid and actinide containing waste solutions while simultaneously separating the actinides
US4563335A (en) * 1982-12-21 1986-01-07 Doryokuro Kakunenryo Kaihatsu Jigyodan Apparatus for continuously concentrating and denitrating nitrate solution by microwave
US4687601A (en) * 1983-11-25 1987-08-18 Comurhex Process for the preparation of pulverulent metallic oxides from metallic nitrates
US4671951A (en) * 1984-03-23 1987-06-09 C-I-L Inc. Purification and reconcentration of waste sulphuric acid
US4673560A (en) * 1985-02-20 1987-06-16 C-I-L Inc. Generation of sulphur trioxide from oleum using microwave energy
US4671952A (en) * 1985-02-20 1987-06-09 C-I-L Inc. Vaporizing liquid sulfur dioxide with microwave radiation
US4737610A (en) * 1985-03-30 1988-04-12 Hugo Petersen Gesellschaft fur verfahrenstechnischen Anlagenbau mbH & Co. KG Method and apparatus for the desorption of an adsorption agent that is loaded with noxious material
US4871479A (en) * 1986-03-25 1989-10-03 Comurhex Societe Pour La Conversion De L'uranium En Metal Et Hexafluorure Process for producing sintered mixed oxides which are soluble in nitric acid from solutions of nitrates
US4873031A (en) * 1986-06-18 1989-10-10 Mitsubishi Kinzoku Kabushiki Kaisha Method of controlling the crystal grain size of uranium dioxide pellet
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GB2019178B (en) 1982-11-10
GB2019178A (en) 1979-10-24
BE874748A (fr) 1979-07-02
DE2909858A1 (de) 1979-09-27
DE2909858C2 (de) 1983-08-04
FR2420269B1 (enrdf_load_stackoverflow) 1984-06-29
JPS6112558B2 (enrdf_load_stackoverflow) 1986-04-09
JPS54121442A (en) 1979-09-20
FR2420269A1 (fr) 1979-10-12

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